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| | author name = Condra D | | | author name = Condra D |
| | author affiliation = Oak Ridge Institute for Science & Education | | | author affiliation = Oak Ridge Institute for Science & Education |
| | addressee name = Kottan J J | | | addressee name = Kottan J |
| | addressee affiliation = NRC/RGN-I | | | addressee affiliation = NRC/RGN-I |
| | docket = 05000247 | | | docket = 05000247 |
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| {{#Wiki_filter:4B ORISE OAK RIDGE INSTITUTE FOR SCIENCE AND EDUCATION I [uly 31. 2007 fir. Jim Kottan J.S. Nuclear Regulatory Commission 1 t?GeLdak Road (Ing of Prussia, PA 19406 | | {{#Wiki_filter:4B O R I S E OAK RIDGE INSTITUTE FOR SCIENCE AND EDUCATION I [uly 31. 2007 fir. Jim Kottan J.S.Nuclear Regulatory Commission 1 t?GeLdak Road (Ing of Prussia, PA 19406 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| REPORT FOR ANALYSES FOR SAMPLES FROM SET TWENTY-FOUR, FROM THE INDIAN POINT POWER STATION, BUCHANAN, NEW | | REPORT FOR ANALYSES FOR SAMPLES FROM SET TWENTY-FOUR, FROM T H E INDIAN POINT POWER STATION, BUCHANAN, NEW I YORK |
| [INSPECTION REPORT NO. 050-247/2007-0031 | | [INSPECTION REPORT NO. 050-247/2007-0031 [RFTA NO. 07-0011 |
| [RFTA NO. 07-0011 I YORK >ear Mr. Icottan: The Oak Ridge Institute for Science and Education (ORISE) recrived sct 24, consisting of six water amples, associated with the Indian Point Power Station on May 11, 2007. Sample analysis was initiated lased on your previous direction for handling samples from ths licrnsee and modified based on a phone :onversation with John \Vhtte on July 3,2007 and an e-mail from Stacie Sakai on July 9, 2007. Sample dentification and collection data for the samples addressed in thts report are presented in Table 1. | | >ear Mr. Icottan: |
| >amma spectroscopy, the hard-to-detect beras (iron-55, nickel-63, and tritium), technetium-99, total .adiostrontium, alpha spectroscopy, plutonium-241, and carbon-14 data are provided in Tables 2 through 3, respectively. | | The Oak Ridge Institute for Science and Education (ORISE) recrived sct 24, consisting of six water amples, associated with the Indian Point Power Station on May 11, 2007. Sample analysis was initiated lased on your previous direction for handling samples from t h s licrnsee and modified based on a phone |
| The pertinent procedure references are provided in each specific table. | | :onversation with John \Vhtte on July 3,2007 and an e-mail from Stacie Sakai on July 9, 2007. Sample dentification and collection data for the samples addressed in thts report are presented in Table 1. |
| 3RISE's Quality Control (QC) requirements were met for these analyses. | | >amma spectroscopy, the hard-to-detect beras (iron-55, nickel-63, and tritium), technetium-99, total |
| The QC fdes are available for Tour review upon requrst. Wy contact information is listed below. You may also contact Wade Ivey at 865.576.9184 with any questions or comments. | | .adiostrontium, alpha spectroscopy, plutonium-241, and carbon-14 data are provided in Tables 2 through 3, respectively. The pertinent procedure references are provided in each specific table. |
| Sincerely, Dale Condra, Manager '>aboratory RDC:LYTI.at Znclosures T. Carter, NRC/FSME/DLVIVIEP 7J8 E. &ox-Davin, NRC/FSME/TWFN S. Roberts, ORISE File 1697 SA23 J. E \Y.htc, NRC Regiot . Abelquist, ORISE zp 75 I W s lg VI Voice: 865.241.3242 Fax: 865.241.3248 E-mail: Dale.Condra | | 3RISE's Quality Control (QC) requirements were met for these analyses. The QC fdes are available for Tour review upon requrst. |
| @orau.org TABLE 1 - ORISE NRC Region I Collection Collection Date Sample ID Sample ID Time 1 697WO 142 Mw-54-38'- | | Wy contact information is listed below. You may also contact Wade Ivey at 865.576.9184 with any questions or comments. |
| (00 1) 5/3/2007 16:19 1697W0143 Mw-54-59'-(001) 5/3/2007 16:45 1697W0144 Mw-54-125'-(001) 5/3/2007 14:18 1697W0145 Mw-54-146'-(001) 5/3/2007 1431 1697W0146 Mw-54-174'-(001) 5/3/2007 1443 1697WO147 Mw-54-192'-(001) 5/3/2007 15:OO SAMPLE IDENTIFICATIONS AND COLLECTION DATA INDIAN POINT POWER STATION BUCHANAN, NEW YORK Indian Point Power Station Projects/l697/Dara Tables/2007-07-31 Interim Data Tables 1697 Set 24 TABLE 2 ORISE Sample ID 1697YV0142 1697M0143 1697YV0144 1697YV0145 CONCENTRATIONS OF SELECTED GAMMA EMITTING RADIONUCLIDES IN WATER SAMPLES BY GAMMA SPECTROSCOPY CP1, REVISION 15 INDIAN POINT POWER STATION BUCWAN, NEW YORK Radionuclide Concentrations, TPUs, and MDCs" @Ci/L)
| | Sincerely, Dale Condra, Manager zp |
| CO-58 CO-60 cs-l34 cs-w7 NRC Region I Sample ID m-54-38'-(001)
| | '>aboratory 75 I |
| O.Ob k 2.0' , 3.5 2.3 k 3.1 , 3.8 0.5 f 2.4 , 3.8 2.4 ? 4.6 , 3.5 m-54-59'-(001)
| | RDC:LYTI.at W Znclosures s T. Carter, NRC/FSME/DLVIVIEP 7J8 E. &ox-Davin, NRC/FSME/TWFN SA23 J. \Y.htc, NRC Regiot E . Abelquist, ORISE lg VI S.Roberts, ORISE File 1697 Voice: 865.241.3242 Fax: 865.241.3248 E-mail: Dale.Condra @orau.org |
| -1.1 2 2.3 , 3.8 -0.2 k 2.2 , 3.9 0.5 2 2.3 , 3.9 -1.0 L 2.2 , 3.6 m-54-125'-(001)
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| -1.1 k 1.8 , 3.1 -0.6 k 1.8 , 3.2 -2.6 -t 1.9 , 3.0 2.1 ? l>j , 3.0 m-54-146'-(001)
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| -1.9 k 2.8 , 4.1 2.4 ? 2.4 , 4.3 -0.8 ? 3.5 , 4.1 -1.0 k 2.3 , 3.8 1) 1697W0146 I m-54-174'-(001)
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| I -1.2 ? 2.2 , 3.5 I 1.9 ? 2.1 , 3.81 -1.2 k 2.4 , 3.7) 1.3 k 4.6 , 3.3 I(
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| TABLE 3 ORISE Sample ID ~ Radionuclide Concentrations, TPUs, and MDCs" @Ci/L)
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| NRC Region I Sample ID Fe-55h Ni-63' H-3* 1697W0142 MW-54-38'-(001)
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| -13 k lge , 33 6.1 i 4.4 , 7.2 1,000 i 210 , 290 InlanPmr Power Statlon 169W0144 1697W0145 1697W0146 1697W0147 - Fra~ectr/l697/DaraTables/2007-07-31 Intern Data Tables 1697 Set 24 I, I Mw-54-125'-(001)
| |
| -6 f 19 , 33 5.2 ? 4.3 , 7.2 1,390 f 220 , 290 MW-54-146'-(001)
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| -4 k 19 , 33 5.7 f 4.3 , 7.2 1,720 k 240 , 290 MW-54-174'-(001)
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| -8 2 19 , 33 8.9 ? 4.4 , 7.2 1,830 ? 240 , 290 Mw-54-192'-(001)
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| -2 k 19 , 33 6.4 k 4.4 , 7.2 1,860 +_ 240 , 290 TABLE 4 ORISE Sample ID CONCENTRATIONS OF TECHNETIUM-99 , IN WATER SAMPLES BY LIQUID SCINTILLATION ANALYSIS AP5, REVISION 17; CP4, REVISION 3 INDIAN POINT POWER STATION BUCHANAN, NEW YORK Radionuclide NRC Region I Concentrations, Sample ID TPUs, and MDCs" @Q/L) b 1697W0142 I MW-54-38'-(001)
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| I 3.1 ? 7.6 , 13.0 (1 1697W0143 1 MW-54-59'-(001)
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| I -1.2 ? 7.5 , 13.0 11 1697W0144 1 MW-54-125'-(001)
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| I 3.5 i 7.7 , 13.0 1) 1697W0145 1 MW-54-146'-(001)
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| I -0.3 k 7.5 . 13.0 I1 .. I1 1697W0146 i Mw-54-174'-(001) 1 4.5 k 7.7 . 13.0 11 1697W0147 I MW-54-192'-1001)
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| I -8.2 ? 7.4 , 13.0 (1 Indlan Point Power stauon Prqetcs/l697/Dara Tabler/Z007-07-31 Intern Data Tables 1697 Set 24 TABLE 5 ORISE Sample ID 1697W0142 1697W0143 1697W0144
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| 1697W0145 1697W0146 1697W0147 Radionuclide Concentrations, TPUs, and MDCS" @Ci/L) NRC Region I Sample ID Mw-54-38'-(001) 12.2 rt l.lb , 0.9 m-54-59'-(001) 3.09 i 0.67 , 0.84 m-54-125'-(001) 21.3 i 1.5 , 0.8 MW-54-146'-(001) 16.9 rt 1.3 , 0.9 MW-54-174'-(001) 19.4 rt 1.4 , 0.9 Mw-54-192'-(001) 22.5 | | TABLE 1 SAMPLE IDENTIFICATIONS AND COLLECTION DATA INDIAN POINT POWER STATION BUCHANAN, NEW YORK ORISE NRC Region I Collection Date Collection Sample ID Sample ID Time 1697WO142 Mw-54-38'-(00 1) 5/3/2007 16:19 1697W0143 Mw-54-59'-(001) 5/3/2007 16:45 1697W0144 Mw-54-125'-(001) 5/3/2007 14:18 1697W0145 Mw-54-146'-(001) 5/3/2007 1431 1697W0146 Mw-54-174'-(001) 5/3/2007 1443 1697WO147 Mw-54-192'-(001) 5/3/2007 15:OO Indian Point Power Station Projects/l697/Dara Tables/2007-07-31 Interim Data Tables 1697 Set 24 |
| * 16 , 0.9 Indian Point Power Station Pr4ects/l697/Data Tables/2007~07-31 Inte- Data Tables 1697 Set 24 TABLE 6 ORISE NRC Region I Sample ID Sample ID 1697W0142 Mw-54-38'-(001) 1697W0143 MW-54-59'-(001) 1697W0144 MW-54-125'-(001) 1697W0145 MW-54-146'-(001) 1697W0146 MW-54-174'-(001) 1697W0147 MW-54-192'-(001)
| | |
| Radionuclide Concentrations' (pCi/L for water) Am-241 Cm-242 Cm-243/244 Np-237 0.11 ? 0.15Ib , 0.32 -0.23 ? 0.19 , 0.41 0.02 ? 0.23 , 0.43 0.05 k 0.08 , 0.14 0.41 t 0.27 , 0.39 -0.02 ? 0.11 , 0.25 -0.07 ? 0.20 , 0.41 0.04 ? 0.08 , 0.16 0.09 0.13 , 0.22 0.00' ? 0.05 , 0.14 0.12 ? 0.09 , 0.05 -0.02 t 0.04 , 0.16 0.21 ? 0.22 , 0.36 0.05 2 0.09 , 0.15 -0.03 ? 0.16 , 0.32 0.02 2 0.09 , 0.19 0.07 ? 0.21 , 0.38 0.00 k 0.10 , 0.22 0.02 ? 0.16 , 0.32 -0.06 ? 0.09 , 0.24 -0.04 ? 0.24 , 0.46 -0.08 ? 0.08 , 0.23 0.00 2 0.19 , 0.38 -0.08 ? 0.13 , 0.32 t B TABLE 6 (Continued) | | TABLE 2 CONCENTRATIONS OF SELECTED GAMMA EMITTING RADIONUCLIDES I N WATER SAMPLES BY GAMMA SPECTROSCOPY CP1, REVISION 15 INDIAN POINT POWER STATION B U C W A N , NEW YORK Radionuclide Concentrations, ORISE NRC Region I TPUs, and MDCs" @Ci/L) |
| CONCENTRATIONS OF SELECTED ALPHA EMITTING RADIONUCLIDES IN DISSOLVED FRACTIONS OF WATER SAMPLES AP11, REVISION 3; CP2, REVISION 12 INDIAN POINT POWER STATION BUCHANAN, NEW YORK i TABLE 7 ORISE NRC Region I CONCENTRATIONS OF PLUTONIUM-241 IN DISSOLVED FRACTIONS OF WATER SAMPLES BY LIQUID SCINTILLATION ANALYSIS APlO, REVISION 3; CP4, REVISION 3 INDIAN POINT POWER STATION BUCHANAN, NEW YORK Radionuclide Concentrations, Sample ID 1697W0142 1697W0143 SampleID TPUs, and MDCs" @Ci/L) | | Sample ID Sample ID CO-58 CO-60 cs-l34 cs-w7 1697YV0142 m-54-38'-(001) O.Ob k 2.0' , 3.5 2.3 k 3.1 , 3.8 0.5 f 2.4 , 3.8 2.4 ? 4.6 , 3.5 1697M0143 m-54-59'-(001) -1.1 2 2.3 , 3.8 -0.2 k 2.2 , 3.9 0.5 2 2.3 , 3.9 -1.0 L 2.2 , 3.6 1697YV0144 m-54-125'-(001) -1.1 k 1.8 , 3.1 -0.6 k 1.8 , 3.2 -2.6 -t 1.9 , 3.0 2.1 ? l>j , 3.0 1697YV0145 m-54-146'-(001) -1.9 k 2.8 , 4.1 2.4 ? 2.4 , 4.3 -0.8 ? 3.5 , 4.1 -1.0 k 2.3 , 3.8 |
| Mw-54-38'-(001) | | : 1) 1697W0146 I m-54-174'-(001) I -1.2 ? 2.2 , 3.5 I 1.9 ? 2.1 , 3.81 -1.2 k 2.4 , 3.7) 1.3 k 4.6 , 3.3 I( |
| -2 | | |
| * 37b 63 Mw-54-59'-(001) 8 | | TABLE 3 |
| * 34 59 Mw-54-125'-(001) 9 i 35 The MDCS are afrer the comma. bUn~ercmoes represmr he 9594 confidence lwd, bascd on total propagated uncertainties 1697W0145 Mw-54-146'-(001) | | ~ |
| Indian Point Power Station 5
| | Radionuclide Concentrations, ORISE N R C Region I TPUs, and MDCs" @Ci/L) |
| * 34 59 Prqlects/l697/Data Tables/2007-07-31 Inte-Data Tables 1697 Set 24 1697W0146 Mw-54-174'-(001) 3 | | Sample ID Sample ID Fe-55h Ni-63' H-3* |
| * 37 63 1697W0147 Mw-54-192'-(001) | | 1697W0142 MW-54-38'-(001) -13 k l g e , 33 6.1 i 4.4 , 7.2 1,000 i 210 , 290 I , |
| -6 t 36 62 TABLE 8 ORISE NRC Region I Sample ID Sample ID Radionuclide Concentrations, TPUs, and MDCs' @Ci/L) 1697W0142 1697W0143 1697W0144 1697W0145 1697W0146 1697W0147 me mcs are after the coma. bUncertmties reprerent the 959b confidence level, based on totdpropagated uncert&mes. | | I 169W0144 Mw-54-125'-(001) -6 f 19 , 33 5.2 ? 4.3 , 7.2 1,390 f 220 , 290 |
| MW-54-38'-(001) | | - 1697W0145 MW-54-146'-(001) -4 k 19 , 33 5.7 f 4.3 , 7.2 1,720 k 240 , 290 1697W0146 MW-54-174'-(001) -8 2 19 , 33 8.9 ? 4.4 , 7.2 1,830 ? 240 , 290 1697W0147 Mw-54-192'-(001) -2 k 19 , 33 6.4 k 4.4 , 7.2 1,860 +_ 240 , 290 InlanPmr Power Statlon I n t e r n Data Tables 1697 Set 24 Fra~ectr/l697/DaraTables/2007-07-31 |
| -0.8 f 9.4b , 16.1 MW-54-59'-(001) | | |
| -7.2 k 9.4 , 16.1 MW-54-125'-(001) | | TABLE 4 CONCENTRATIONS OF TECHNETIUM-99 |
| -6.0 f 9.4 , 16.1 MW-54-146'-(001) 0.3 f 9.5 , 16.1 MW-54-174'-(001) | | , I N WATER SAMPLES BY LIQUID SCINTILLATION ANALYSIS AP5, REVISION 17; CP4, REVISION 3 INDIAN POINT POWER STATION BUCHANAN, NEW YORK Radionuclide ORISE NRC Region I Concentrations, Sample ID Sample ID TPUs, and MDCs" |
| -1.7 f 9.4 , 16.1 ME-54-1 92'-(001) | | @Q/L) 1697W0142 I MW-54-38'-(001) I 3.1 ? 7.6b , 13.0 (1 1697W0143 1 MW-54-59'-(001) I -1.2 ? 7.5 , 13.0 1 1 I 11I) 1697W0144 1697W0145 1697W0146 1 |
| -5.3 i 9.4 , 16.1 - In&m Pomr Power stauon Pr~ects/lG9l/Data Tabler/2007-07-31 InteMl DataTables 1697 Set 24}} | | i MW-54-125'-(001) |
| | MW-54-146'-(001) |
| | Mw-54-174'-(001) |
| | I 1 |
| | 3.5 |
| | -0.3 4.5 i 7.7 k 7.5 k 7.7 |
| | , 13.0 13.0 13.0 1I 11 1697W0147 I MW-54-192'-1001) I -8.2 ? 7.4 , 13.0 (1 Indlan Point Power stauon Prqetcs/l697/Dara Tabler/Z007-07-31 I n t e r n Data Tables 1697 Set 24 |
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| | TABLE 5 Radionuclide ORISE NRC Region I Concentrations, TPUs, and Sample ID Sample ID MDCS" @Ci/L) 1697W0142 Mw-54-38'-(001) 12.2 rt l.lb , 0.9 1697W0143 m-54-59'-(001) 3.09 i 0.67 , 0.84 1697W0144 m-54-125'-(001) 21.3 i 1.5 , 0.8 1697W0145 MW-54-146'-(001) 16.9 rt 1.3 , 0.9 1697W0146 MW-54-174'-(001) 19.4 rt 1.4 , 0.9 1697W0147 Mw-54-192'-(001) 22.5 |
| | * 1 6 , 0.9 Indian Point Power Station Pr4ects/l697/Data Tables/2007~07-31Inte- Data Tables 1697 Set 24 |
| | |
| | TABLE 6 ORISE NRC Region I Radionuclide Concentrations' (pCi/L for water) |
| | Sample ID Sample ID Am-241 Cm-242 Cm-243/244 Np-237 1697W0142 Mw-54-38'-(001) 0.11 ? 0.15Ib , 0.32 -0.23 ? 0.19 , 0.41 0.02 ? 0.23 , 0.43 0.05 k 0.08 , 0.14 1697W0143 MW-54-59'-(001) 0.41 t 0.27 , 0.39 -0.02 ? 0.11 , 0.25 -0.07 ? 0.20 , 0.41 0.04 ? 0.08 , 0.16 1697W0144 MW-54-125'-(001) 0.09 0.13 , 0.22 0.00' ? 0.05 , 0.14 0.12 ? 0.09 , 0.05 -0.02 t 0.04 , 0.16 1697W0145 MW-54-146'-(001) 0.21 ? 0.22 , 0.36 0.05 2 0.09 , 0.15 -0.03 ? 0.16 , 0.32 0.02 2 0.09 , 0.19 1697W0146 MW-54-174'-(001) 0.07 ? 0.21 , 0.38 0.00 k 0.10 , 0.22 0.02 ? 0.16 , 0.32 -0.06 ? 0.09 , 0.24 1697W0147 MW-54-192'-(001) -0.04 ? 0.24 , 0.46 -0.08 ? 0.08 , 0.23 0.00 2 0.19 , 0.38 -0.08 ? 0.13 , 0.32 t |
| | B |
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| | TABLE 6 (Continued) |
| | CONCENTRATIONS OF SELECTED ALPHA EMITTING RADIONUCLIDES IN DISSOLVED FRACTIONS OF WATER SAMPLES AP11, REVISION 3; CP2, REVISION 12 INDIAN POINT POWER STATION BUCHANAN, NEW YORK i |
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| | TABLE 7 CONCENTRATIONS OF PLUTONIUM-241 I N DISSOLVED FRACTIONS OF WATER SAMPLES BY LIQUID SCINTILLATION ANALYSIS APlO, REVISION 3; CP4, REVISION 3 INDIAN POINT POWER STATION BUCHANAN, NEW YORK ORISE NRC Region I Radionuclide Concentrations, Sample ID SampleID TPUs, and MDCs" @Ci/L) 1697W0142 Mw-54-38'-(001) -2 |
| | * 37b 63 1697W0143 Mw-54-59'-(001) 8 |
| | * 34 59 Mw-54-125'-(001) 9 i 35 1697W0145 Mw-54-146'-(001) 5 |
| | * 34 59 1697W0146 Mw-54-174'-(001) 3 |
| | * 37 63 1697W0147 Mw-54-192'-(001) -6 t 36 62 T h e MDCS are afrer the comma. |
| | bUn~ercmoesrepresmr h e 9594 confidence lwd, bascd on total propagated uncertainties Indian Point Power Station Prqlects/l697/Data Tables/2007-07-31 Inte-Data Tables 1697 Set 24 |
| | |
| | TABLE 8 ORISE NRC Region I Radionuclide Concentrations, Sample ID Sample ID TPUs, and MDCs' @Ci/L) 1697W0142 MW-54-38'-(001) -0.8 f 9.4b , 16.1 1697W0143 MW-54-59'-(001) -7.2 k 9.4 , 16.1 - |
| | 1697W0144 MW-54-125'-(001) -6.0 f 9.4 , 16.1 1697W0145 MW-54-146'-(001) 0.3 f 9.5 , 16.1 1697W0146 MW-54-174'-(001) -1.7 f 9.4 , 16.1 1697W0147 ME-54-192'-(001) -5.3 i 9.4 , 16.1 m e m c s are after the c o m a . |
| | bUncertmties reprerent the 959b confidence level, based on totdpropagated uncert&mes. |
| | In&m Pomr Power stauon Pr~ects/lG9l/DataTabler/2007-07-31 InteMl DataTables 1697 Set 24}} |
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MF3313 and MF3314) NL-16-035, Supplemental to Basis for Performance of the Mitigating Strategies Assessment with Flood Hazard Information & Report for Recommendations 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accid2016-04-0505 April 2016 Supplemental to Basis for Performance of the Mitigating Strategies Assessment with Flood Hazard Information & Report for Recommendations 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accid ML16056A1392016-03-11011 March 2016 Correction to the U.S. Nuclear Regulatory Commission Analysis of Licensees' Decommissioning Funding Status Reports NL-15-019, Reply to Request for Additional Information 3.0.3-2 from Set 2014-01 for the Review of the License Renewal Application2015-03-10010 March 2015 Reply to Request for Additional Information 3.0.3-2 from Set 2014-01 for the Review of the License Renewal Application ML11221A3052011-08-0909 August 2011 Lr Hearing - NIA-078 NL-11-013, Revised Tables from Responses to Requests for Exemption from 10 CFR 50, Appendix R, Paragraph III.G.2 for Use of Operator Manual Actions2011-02-10010 February 2011 Revised Tables from Responses to Requests for Exemption from 10 CFR 50, Appendix R, Paragraph III.G.2 for Use of Operator Manual Actions ML0936409322009-12-30030 December 2009 Table I, Structural Heat Sinks, Table II, Containment Heat Sink Thermodynamic Data NL-09-151, Telephone Conference Call Regarding Met Tower Data for SAMA Analysis2009-11-16016 November 2009 Telephone Conference Call Regarding Met Tower Data for SAMA Analysis NL-09-018, Reply to Request for Additional Information - Miscellaneous Items2009-01-27027 January 2009 Reply to Request for Additional Information - Miscellaneous Items ML11221A3032008-12-22022 December 2008 Lr Hearing - NIA-077 NL-08-144, Program for Maintenance of Irradiated Fuel and Preliminary Decommissioning Cost Analysis in Accordance with 10 CFR 50.54 (Bb) and 10 CFR 50.75(f)(3)2008-10-23023 October 2008 Program for Maintenance of Irradiated Fuel and Preliminary Decommissioning Cost Analysis in Accordance with 10 CFR 50.54 (Bb) and 10 CFR 50.75(f)(3) ML0905604702008-08-31031 August 2008 Long-Term Monitoring Plan Position Paper ML11221A1262008-08-14014 August 2008 Lr Hearing - NIA-076, Table 1, Projections of the Population and Components of Change for Us: 2010 to 2050 ENOC-08-00040, Commitment Update Relating to Application for Order Approving Indirect Transfer of Control of Licenses2008-07-28028 July 2008 Commitment Update Relating to Application for Order Approving Indirect Transfer of Control of Licenses ML0904006772008-07-0101 July 2008 Unit 3 SBO Event: Time Line to Energize Unit 3 Bus from App R Diesel Via Gt/Bt ML0904006972008-07-0101 July 2008 SBO Event: Time Line to Energize a 480V Bus from GT-25/26 and App R Diesel ML0904100382008-07-0101 July 2008 SBO Event: Time Line to Energize 480V Bus 6A from GT-25/26 and App R Diesel (Total Time: 47 Minutes) ML0904100962008-07-0101 July 2008 ECN 7385; Attachment 7.46 - Post MOD Test Plan ML0904104002008-06-17017 June 2008 Vendor Data for 24-Hr. Run; Entergy, Buchanan, Ny ML0814804812008-05-27027 May 2008 NRC Graphics - Indian Point ML0905101052008-05-0505 May 2008 Trend Report for Nuclides: Co-60, Cs-137, H-3, Ni-63, Sr-90 ML0905101062008-05-0505 May 2008 M10 Investigation Wells NL-08-074, Amendment 4 to License Renewal Application (LRA) Letter Dated April 30, 2008 from Entergy Nuclear Northeast (NL-08-074)2008-04-30030 April 2008 Amendment 4 to License Renewal Application (LRA) Letter Dated April 30, 2008 from Entergy Nuclear Northeast (NL-08-074) ML0905401352008-01-10010 January 2008 Ground Water Monitoring Well Information Table ML0905102022008-01-0808 January 2008 Groundwater Investigation - Summary NYS Results as of 01/08/2008 ML0736200892007-12-20020 December 2007 Report for Analysis or Eight Water Samples from Set 6 from the Indian Point Power Station, Buchanan, New York Dated December 20, 2007 ENOC-07-00036, Entergy Operations, Inc. - Supplemental Information in Support of Application for Order Approving Indirect Transfer of Control of Licenses2007-10-31031 October 2007 Entergy Operations, Inc. - Supplemental Information in Support of Application for Order Approving Indirect Transfer of Control of Licenses ML0731801672007-10-18018 October 2007 Report for Analysis of Seven Water Samples from Set Five from the Indian Point Power Station, Buchanan, New York, Dtd October 18, 2007 ML0728203072007-10-11011 October 2007 Electronic Distribtion Initiative Letter, Licensee List, Electronic Distribution Input Information, Division Plant Mailing Lists ML0729502532007-10-10010 October 2007 Siren Schedule 11 X 17 Dtd 10/10/07 ML0728403122007-07-31031 July 2007 Report for Analysis for Samples from Set Twenty-Four from the Indian Point Power Station, Buchanan, New York. Dtd. July 31, 2007 ML0728402552007-05-0303 May 2007 Interim Report for Completed Analysis for Samples from Set Twenty-One from the Indian Point Power Station, Buchanan, New York. Dtd. May 3, 2007 ML0713102862007-03-20020 March 2007 E-Mail from D. Winslow of GZA to M. Barvenik of GZA, J. Noggle of USNRC and J. Adler of Entergy, Regarding GZA Results ML0713100562007-02-15015 February 2007 E-Mail from T. Rice of NYSDEC to Various, Regarding Latest State Results ML0713100452007-02-12012 February 2007 E-Mail from P. Donahue of Entergy to T. Rice of NYSDEC, Regarding Split Sample Data ML0713005932007-01-24024 January 2007 E-Mail from D. Gray of Entergy to J. Noggle of USNRC, Regarding Historical Sr Data ML0709405042007-01-12012 January 2007 Ltr from Orise Dtd 01/12/2007, Final Letter Report for Requested Analyses of Six Water Samples, Set Eleven, from the Indian Point Power Station, Buchanan, New York (Inspection Report No. 05000247/2006-007) (Rfta No. 06-001) IR 05000247/20060072007-01-0404 January 2007 Ltr from Orise Dtd 01/04/2007, Final Letter Report for Requested Analyses of Nine Water Samples, Set Nine, from the Indian Point Power Station, Buchanan, New York (Inspection Report No. 05000247/2006007) (Rfta No. 06-001) ML0709406182007-01-0404 January 2007 Ltr from Orise Dtd 01/04/2007, Final Letter Report for Requested Analyses of Nine Water Samples, Set Nine, from the Indian Point Power Station, Buchanan, New York (Inspection Report No. 05000247/2006007) (Rfta No. 06-001) ML0701105612006-12-15015 December 2006 Interim Report for Completed Analyses for Samples from Sets Fifteen and Sixteen, from the Indian Point Power Station, Buchanan, New York. (Inspection Report No. 050-247/2006-007) (Rfta No. 06-001) ML0704003112006-12-0404 December 2006 E-Mail from T. Rice of Department of Environmental Conservation to J. Adler of Entergy, and J. Noggle and J. White of USNRC, Regarding Latest State Data ML0704002992006-11-28028 November 2006 E-Mail from T. Rice of Department of Environmental Conservation to Various, Regarding Latest State Results ML0701105482006-11-17017 November 2006 Interim Report for Requested Analyses for Samples from Sets Eleven Through Fourteen, from the Indian Point Power Station, Buchanan, New York. (Inspection Report No. 050-247/2006-007) (Rfta No. 06-001) ML0628302122006-06-15015 June 2006 E-mail from R. Lavera of Entergy to J. Noggle of NRC, Regarding Sample Log ML0618605182006-04-26026 April 2006 E-mail from R. Sachatello of Entergy to M. Barvenik and D. Sinslow of GZA, Regarding Pressure Test Discussion with GZA ML0620001512006-04-13013 April 2006 E-mail from K. Mcmullian, Entergy, to J. Boska, NRR, Et Al., IPEC Status Report April 13 ML0610006912006-03-27027 March 2006 Units 1 & 2 Tritium History (GL-80-10), in Nci/Ml ML0610006872006-03-27027 March 2006 Fsb Sample Log 2018-03-19
[Table view] Category:Letter
MONTHYEARML24011A1982024-01-12012 January 2024 ISFSI, Notice of Organization Change for Site Vice President ML23342A1082024-01-0909 January 2024 Independent Spent Fuel Storage Installation Security Inspection Plan ML23353A1742023-12-19019 December 2023 ISFSI, Emergency Plan, Revision 23-04 L-23-019, Proof of Financial Protection 10 CFR 140.152023-12-18018 December 2023 Proof of Financial Protection 10 CFR 140.15 ML23339A0442023-12-0505 December 2023 Issuance of Amendment No. 68, 301 and 277 Regarding Changes to Implement the Independent Spent Fuel Storage Installation Physical Security Plan ML23326A1322023-12-0505 December 2023 Issuance of Amendment No. 67, 300 & 276 to Implement the Independent Spent Fuel Storage Installation Only Emergency Plan ML23338A2262023-12-0404 December 2023 Signed Amendment No. 27 to Indemnity Agreement No. B-19 ML23356A0212023-12-0101 December 2023 American Nuclear Insurers, Secondary Financial Protection (SFP) Program ML23242A2772023-11-30030 November 2023 NRC Letter Issuance - IP LAR for Units 2 and 3 Renewed Facility Licenses and PDTS to Reflect Permanent Removal of Spent Fuel from SFPs ML23338A0482023-11-30030 November 2023 ISFSI, Report of Changes to Physical Security, Training and Qualification, Safeguards Contingency Plan, and ISFSI Security Program, Revision 28 ML22339A1572023-11-27027 November 2023 Letter - Indian Point - Ea/Fonsi Request for Exemptions from Certain Emergency Planning Requirements for 10 CFR 50.47 and 10 CFR Part 50, Appendix E IR 05000003/20230032023-11-21021 November 2023 NRC Inspection Report Nos. 05000003/2023003, 05000247/2023003, 05000286/2023003, and 07200051/2023003 ML23100A1172023-11-17017 November 2023 NRC Response - Indian Point Energy Center Generating Units 1, 2, and 3 Letter with Enclosures Regarding Changes to Remove the Cyber Security Plan License Condition ML23050A0032023-11-17017 November 2023 Letter - Issuance Indian Point Unit 2 License Amendment Request to Modify Tech Specs for Staffing Requirements Following Spent Fuel Transfer to Dry Storage ML23100A1252023-11-17017 November 2023 Letter and Enclosure 1 - Issuance Indian Point Energy Center Units 1, 2, and 3 Exemption for Offsite Primary and Secondary Liability Insurance Indemnity Agreement ML23100A1432023-11-16016 November 2023 Letter - Issuance Indian Point Energy Center Generating Units 1, 2, and 3 Exemption Concerning Onsite Property Damage Insurance (Docket Nos. 50-003, 50-247, 50-286) ML23064A0002023-11-13013 November 2023 NRC Issuance for Approval-Indian Point EC Units 1, 2 and 3 Emergency Plan and Emergency Action Level Scheme Amendments L-23-012, Master Decommissioning Trust Agreement Changes for Indian Point Nuclear Generating Units 1, 2 and 3, Pilgrim Nuclear Power Station, Palisades Nuclear Plant and the Non-Qualified Trust for Big Rock Point2023-11-13013 November 2023 Master Decommissioning Trust Agreement Changes for Indian Point Nuclear Generating Units 1, 2 and 3, Pilgrim Nuclear Power Station, Palisades Nuclear Plant and the Non-Qualified Trust for Big Rock Point ML23306A0992023-11-0202 November 2023 and Indian Point Energy Center, Notification of Changes in Schedule in Accordance with 10 CFR 50.82(a)(7) ML23063A1432023-11-0101 November 2023 Letter - Issuance Holtec Request for Indian Point Energy Center Generating Units 1, 2, and 3 Exemptions from Certain Emergency Planning Requirements of 10 CFR 50.47 and Part 50 ML23292A0262023-10-19019 October 2023 LTR-23-0211-RI Thomas Congdon, Executive Deputy, Department of Public Service, Chair, Indian Point Decommissioning Oversight Board, Letter Independent Spent Fuel Storage Installation Inspection and Office of the Inspector General Report-RI ML23289A1582023-10-16016 October 2023 Decommissioning International - Registration of Spent Fuel Casks and Notification of Permanent Removal of All Indian Point Unit 3 Spent Fuel Assemblies from the Spent Fuel Pit ML23270A0082023-09-27027 September 2023 Registration of Spent Fuel Casks ML23237A5712023-09-22022 September 2023 09-22-2023 Letter to Dwaine Perry, Chief, Ramapo Munsee Nation, from Chair Hanson, Responds to Letter Regarding Opposition of the Release and Dumping of Radioactive Waste from Indian Point Nuclear Power Plant Into the Hudson River ML23242A2182023-09-12012 September 2023 IPEC NRC Response to the Town of New Windsor, Ny Board Certified Motion Letter Regarding Treated Water Release from IP Site (Dockets 50-003, 50-247, 50-286) ML23250A0812023-09-0707 September 2023 Registration of Spent Fuel Casks ML23255A0142023-08-31031 August 2023 LTR-23-0211 Thomas Congdon, Executive Deputy, Department of Public Service, Chair, Indian Point Decommissioning Oversight Board, Letter Independent Spent Fuel Storage Installation Inspection and Office of the Inspector General Report IR 05000003/20230022023-08-22022 August 2023 NRC Inspection Report 05000003/2023002, 05000247/2023002, 05000286/2023002, and 07200051/2023002 ML23227A1852023-08-15015 August 2023 Request for a Revised Approval Date Regarding the Indian Point Energy Center Permanently Defueled Emergency Plan and Emergency Action Level Scheme ML23222A1442023-08-10010 August 2023 Registration of Spent Fuel Casks ML23208A1642023-07-26026 July 2023 Village of Croton-on-Hudson New York Letter Dated 7-26-23 Re Holtec Wastewater ML23200A0422023-07-19019 July 2023 Registration of Spent Fuel Casks ML23235A0602023-07-17017 July 2023 LTR-23-0194 Dwaine Perry, Chief, Ramapo Munsee Nation, Ltr Opposition of the Release and Dumping of Radioactive Waste from Indian Point Nuclear Power Plant Into the Hudson River ML23194A0442023-07-11011 July 2023 Clarification for Indian Point Energy Center License Amendment Request, Independent Spent Fuel Storage Installation Physical Security Plan ML23192A1002023-07-11011 July 2023 Response to Request for Additional Information Regarding License Amendment Request to Revise the Emergency Plan and Emergency Action Level Scheme ML23171B0432023-06-23023 June 2023 Letter - Indian Point Energy Center - Request for Additional Information for Independent Spent Fuel Storage Installation Facility-Only Emergency Plan License Amendment ML23118A0972023-06-0606 June 2023 06-06-23 Letter to the Honorable Michael V. Lawler, Et Al., from Chair Hanson Regarding Holtec'S Announcement to Expedite Plans to Release Over 500,000 Gallons of Radioactive Wastewater from Indian Point Energy Center Into the Hudson River ML23144A3512023-05-25025 May 2023 Clementina Bartolotta of Pearl River, New York Email Against Treated Water Release from Indian Point Site ML23144A3522023-05-25025 May 2023 Loredana Bidmead of New York E-Mail Against Treated Water Release from Indian Point Site ML23144A3412023-05-25025 May 2023 Dianne Schirripa of Rockland County, New York Email Against Treated Water Release from Indian Point Site ML23144A3472023-05-25025 May 2023 David Mart of Blauvelt, New York Email Against Treated Water Release from Indian Point Site ML23144A3402023-05-25025 May 2023 Melvin Israel of New York Email Against Treated Water Release from Indian Point Site ML23144A3542023-05-25025 May 2023 Terri Thal of New City, New York Email Against Treated Water Release from Indian Point Site ML23144A3532023-05-25025 May 2023 John Shaw of New York Email Against Treated Water Release from Indian Point Site 2024-01-09
[Table view] Category:Report
MONTHYEARML22013A7062022-01-13013 January 2022 Investigation Report of LLRW Shipment Pursuant to 10 CFR 20, Appendix G ML21056A0782021-04-0707 April 2021 Final Environmental Assessment and Finding of No Significant Impact for Initial and Updated Decommissioning Funding Plans for Indian Point ISFSI (Docket: 72-51) NL-21-006, Relief Request IP3-ISI-RR-16, Proposed Alternative to American Society of Mechanical Engineers Code Case N-513-4 Inspection Requirement2021-02-10010 February 2021 Relief Request IP3-ISI-RR-16, Proposed Alternative to American Society of Mechanical Engineers Code Case N-513-4 Inspection Requirement ML20259A2172020-09-14014 September 2020 Commitment Change Summary Report ML20260H0722020-06-18018 June 2020 IP-RPT-14-00013, Revision 3, Indian Point Nuclear Generating Units 2 and 3, Consequences of a Postulated Fire and Explosion Following the Release of Natural Gas from the New Aim 42 Pipeline Near Ipec ML20122A1052020-05-27027 May 2020 Letter from Margaret M. Doane to John B. Rhodes, Chair and Executive Officer, Ny State Public Service Commission: Response to Ny State Public Service Commission Regarding Natural Gas Transmission Pipelines Near Indian Point Nuclear Power Pl ML20100F6352020-04-0808 April 2020 Expert Team Final Report NL-19-073, Request for Relaxation of Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2019-10-22022 October 2019 Request for Relaxation of Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) ML19252A3182019-09-0909 September 2019 Entergy to NRC, IPEC Weekly Sturgeon Monitoring Report for Week of Sept 2, 2019 NL-19-061, Form OAR-1 Owners Activity Report for Inservice Inspection and Repairs and Replacements2019-06-13013 June 2019 Form OAR-1 Owners Activity Report for Inservice Inspection and Repairs and Replacements ML19114A0742019-04-22022 April 2019 Entergy to NRC, IPEC Weekly Sturgeon Monitoring Report for Week of April 15, 2019 NL-19-012, Request for Approval of a Certified Fuel Handler Training and Retraining Program2019-04-15015 April 2019 Request for Approval of a Certified Fuel Handler Training and Retraining Program ML18098A0882018-04-0606 April 2018 Fracture Mechanics Assessment of Embedded Flaw Repair Acceptability NL-18-021, Indian Point, Unit 2, Fracture Mechanics Assessment of Embedded Flaw Repair Acceptability2018-04-0606 April 2018 Indian Point, Unit 2, Fracture Mechanics Assessment of Embedded Flaw Repair Acceptability NL-20-066, Engineering Report IP-RPT-11-00032, Revision 5, Licensing Report on the Inter-Unit Transfer of Spent Nuclear Fuel at the Indian Point Energy Center2017-12-19019 December 2017 Engineering Report IP-RPT-11-00032, Revision 5, Licensing Report on the Inter-Unit Transfer of Spent Nuclear Fuel at the Indian Point Energy Center ML17349A1562017-12-0808 December 2017 Risk Impact of One-Time Extending the ILRT Interval Associated with the Proposed Technical Specification Changes ML17279A2472017-10-0606 October 2017 2017 Annual Assessment Meeting Written Comments Compilation ML17222A2392017-10-0404 October 2017 NRC Response to Request for Deferral of Actions Related to Beyond-Design-Basis Seismic and Flooding Hazard Reevaluations ML17289A6552017-10-0202 October 2017 Attachment 6 to NL-17-115, Revised HI-2094289, Licensing Report on the Inter-Unit Transfer of Spent Fuel at the Energy Center, Revision 9 NL-17-122, Transmittal of 10 CFR 50.59(d)(2) Summary Report, March 26, 2015 to May 18,20172017-09-28028 September 2017 Transmittal of 10 CFR 50.59(d)(2) Summary Report, March 26, 2015 to May 18,2017 ML17096A2122017-03-23023 March 2017 Entergy Engineering Report No. IP-RPT-16-00078, Indian Point RAI CLI-16-07 SAMA Cost-Benefit Sensitivities Rev. 1 (March 23, 2017) NL-17-020, License Renewal Application - Revisions to Reactor Vessel Internals Aging Management Program and Inspection Plan2017-02-0606 February 2017 License Renewal Application - Revisions to Reactor Vessel Internals Aging Management Program and Inspection Plan ML17096A2112017-01-0404 January 2017 Entergy Engineering Report No. IP-RPT-16-00077, Indian Point RAI CLI-16-07 MACCS2 Sensitivities, Rev. 0 (Jan 4, 2017) ML16280A2282016-09-19019 September 2016 Indian Point 2 Technical Requirements Manual NL-16-109, Indian Point 2 Technical Requirements Manual2016-09-19019 September 2016 Indian Point 2 Technical Requirements Manual NL-16-109, HI-2094289, Licensing Report on the Inter-Unit Transfer of Spent Fuel at the Indian Point Energy Center.2016-09-19019 September 2016 HI-2094289, Licensing Report on the Inter-Unit Transfer of Spent Fuel at the Indian Point Energy Center. ML16250A2762016-09-13013 September 2016 Evaluation of Impacts to Proposed Critical Habitat for the Atlantic Sturgeon for Indian Point Nuclear Generating Units 2 and 3 Proposed License Renewal NL-16-083, Post Accident Monitoring (PAM) Report for an Inoperable Containment Area Radiation Monitor (R-26) High Range, Indian Point Unit Number 32016-08-0101 August 2016 Post Accident Monitoring (PAM) Report for an Inoperable Containment Area Radiation Monitor (R-26) High Range, Indian Point Unit Number 3 ML18115A0592016-06-28028 June 2016 After Action Report/Improvement Plan, Drill Date June 28, 2016 ML17052A2662015-10-0202 October 2015 Sturgeon Mobile Tracking for the New Ny Bridge at Tappan Zee NL-15-128, Submittal of 10 CFR 50.59(d)(2) Summary Report of Changes, Tests and Experiments Implemented Between 04/01/2013 and 03/25/2015, And/Or Utilized in Support of the UFSAR Update2015-09-28028 September 2015 Submittal of 10 CFR 50.59(d)(2) Summary Report of Changes, Tests and Experiments Implemented Between 04/01/2013 and 03/25/2015, And/Or Utilized in Support of the UFSAR Update NL-15-118, Post Accident Monitoring (PAM) Report for an Inoperable Reactor Vessel Level Indication System (RVLIS) Train B, Indian Point Unit 32015-09-0303 September 2015 Post Accident Monitoring (PAM) Report for an Inoperable Reactor Vessel Level Indication System (RVLIS) Train B, Indian Point Unit 3 NL-15-099, Submittal of 2014 Annual 10 CFR 50.46 Emergency Core Cooling System Evaluation Changes Report2015-07-30030 July 2015 Submittal of 2014 Annual 10 CFR 50.46 Emergency Core Cooling System Evaluation Changes Report NL-15-072, 2015 Form OAR-1 Owners Activity Report for Inservice Inspection and Repairs and Replacements2015-06-18018 June 2015 2015 Form OAR-1 Owners Activity Report for Inservice Inspection and Repairs and Replacements NL-15-030, Revised 10 C.F.R. 50.59 Safety Evaluation and Supporting Analyses Prepared in Response to the Algonquin Incremental Market Natural Gas Project2015-04-0808 April 2015 Revised 10 C.F.R. 50.59 Safety Evaluation and Supporting Analyses Prepared in Response to the Algonquin Incremental Market Natural Gas Project NL-15-029, Summary of Analysis Results Based on Corrected Format 2 Data Files Dated March 20152015-04-0606 April 2015 Summary of Analysis Results Based on Corrected Format 2 Data Files Dated March 2015 ML15062A2002015-02-19019 February 2015 NET-300067-01, Revision 1, Criticality Safety Analysis of the Indian Point, Unit 2 Spent Fuel Pool with Credit for Inserted Neutron Absorber Panels. (Non-Proprietary) NL-15-013, Re-Submittal of Netco Report NET-300067-01, Criticality Safety Analysis of the Indian Point Unit 2 Spent Fuel Pool with Credit for Inserted Neutron Absorber Panels, for NRC Review and Approval2015-01-28028 January 2015 Re-Submittal of Netco Report NET-300067-01, Criticality Safety Analysis of the Indian Point Unit 2 Spent Fuel Pool with Credit for Inserted Neutron Absorber Panels, for NRC Review and Approval ML15061A2772014-12-31031 December 2014 WCAP-17954-NP, Revision 0, Indian Point Unit 3 Heatup and Cooldown Limit Curves for Normal Operation. NL-14-152, Entergy'S Expedited Seismic Evaluation Process Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights From...2014-12-22022 December 2014 Entergy'S Expedited Seismic Evaluation Process Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights From... ML14329A1952014-11-0404 November 2014 NET-300067-01, Rev. 0, Criticality Safety Analysis of the Indian Point Unit 2 Spent Fuel Pool with Credit for Inserted Neutron Absorber Panels NL-14-115, 10 CFR 50.59(d)(2) Summary Report for Indian Point, Units 1 and 2 April 1, 2012 to March 19, 20142014-09-18018 September 2014 10 CFR 50.59(d)(2) Summary Report for Indian Point, Units 1 and 2 April 1, 2012 to March 19, 2014 ML14304A7012014-09-16016 September 2014 Reliability Needs Assessment ML15166A0702014-08-31031 August 2014 Algonquin Incremental Market (Aim) Project, Phase 2 Acoustic Survey for Indiana Bats (Myotis Sodalis) and Northern Long-Eared Bats (Myotis Septentrionalis), August 2014 NL-14-110, Third Six-Month Status Report for the Implementation of Order EA-12-049 Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events2014-08-27027 August 2014 Third Six-Month Status Report for the Implementation of Order EA-12-049 Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events NL-14-071, Indian Point, Unit 2 - Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 3 of 52014-06-0505 June 2014 Indian Point, Unit 2 - Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 3 of 5 NL-14-071, Indian Point, Unit 2 - Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 2 of 52014-06-0505 June 2014 Indian Point, Unit 2 - Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 2 of 5 ML14168A0592014-06-0505 June 2014 Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 1 of 5 ML14168A0602014-06-0505 June 2014 Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 2 of 5 ML14168A0612014-06-0505 June 2014 Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 3 of 5 2022-01-13
[Table view] Category:Miscellaneous
MONTHYEARML22013A7062022-01-13013 January 2022 Investigation Report of LLRW Shipment Pursuant to 10 CFR 20, Appendix G ML20260H0722020-06-18018 June 2020 IP-RPT-14-00013, Revision 3, Indian Point Nuclear Generating Units 2 and 3, Consequences of a Postulated Fire and Explosion Following the Release of Natural Gas from the New Aim 42 Pipeline Near Ipec ML20122A1052020-05-27027 May 2020 Letter from Margaret M. Doane to John B. Rhodes, Chair and Executive Officer, Ny State Public Service Commission: Response to Ny State Public Service Commission Regarding Natural Gas Transmission Pipelines Near Indian Point Nuclear Power Pl NL-19-073, Request for Relaxation of Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2019-10-22022 October 2019 Request for Relaxation of Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) ML19252A3182019-09-0909 September 2019 Entergy to NRC, IPEC Weekly Sturgeon Monitoring Report for Week of Sept 2, 2019 NL-19-061, Form OAR-1 Owners Activity Report for Inservice Inspection and Repairs and Replacements2019-06-13013 June 2019 Form OAR-1 Owners Activity Report for Inservice Inspection and Repairs and Replacements ML19114A0742019-04-22022 April 2019 Entergy to NRC, IPEC Weekly Sturgeon Monitoring Report for Week of April 15, 2019 NL-19-012, Request for Approval of a Certified Fuel Handler Training and Retraining Program2019-04-15015 April 2019 Request for Approval of a Certified Fuel Handler Training and Retraining Program ML17279A2472017-10-0606 October 2017 2017 Annual Assessment Meeting Written Comments Compilation ML17222A2392017-10-0404 October 2017 NRC Response to Request for Deferral of Actions Related to Beyond-Design-Basis Seismic and Flooding Hazard Reevaluations NL-17-020, License Renewal Application - Revisions to Reactor Vessel Internals Aging Management Program and Inspection Plan2017-02-0606 February 2017 License Renewal Application - Revisions to Reactor Vessel Internals Aging Management Program and Inspection Plan NL-16-083, Post Accident Monitoring (PAM) Report for an Inoperable Containment Area Radiation Monitor (R-26) High Range, Indian Point Unit Number 32016-08-0101 August 2016 Post Accident Monitoring (PAM) Report for an Inoperable Containment Area Radiation Monitor (R-26) High Range, Indian Point Unit Number 3 NL-15-128, Submittal of 10 CFR 50.59(d)(2) Summary Report of Changes, Tests and Experiments Implemented Between 04/01/2013 and 03/25/2015, And/Or Utilized in Support of the UFSAR Update2015-09-28028 September 2015 Submittal of 10 CFR 50.59(d)(2) Summary Report of Changes, Tests and Experiments Implemented Between 04/01/2013 and 03/25/2015, And/Or Utilized in Support of the UFSAR Update NL-15-118, Post Accident Monitoring (PAM) Report for an Inoperable Reactor Vessel Level Indication System (RVLIS) Train B, Indian Point Unit 32015-09-0303 September 2015 Post Accident Monitoring (PAM) Report for an Inoperable Reactor Vessel Level Indication System (RVLIS) Train B, Indian Point Unit 3 NL-15-099, Submittal of 2014 Annual 10 CFR 50.46 Emergency Core Cooling System Evaluation Changes Report2015-07-30030 July 2015 Submittal of 2014 Annual 10 CFR 50.46 Emergency Core Cooling System Evaluation Changes Report NL-15-072, 2015 Form OAR-1 Owners Activity Report for Inservice Inspection and Repairs and Replacements2015-06-18018 June 2015 2015 Form OAR-1 Owners Activity Report for Inservice Inspection and Repairs and Replacements NL-15-030, Revised 10 C.F.R. 50.59 Safety Evaluation and Supporting Analyses Prepared in Response to the Algonquin Incremental Market Natural Gas Project2015-04-0808 April 2015 Revised 10 C.F.R. 50.59 Safety Evaluation and Supporting Analyses Prepared in Response to the Algonquin Incremental Market Natural Gas Project NL-15-013, Re-Submittal of Netco Report NET-300067-01, Criticality Safety Analysis of the Indian Point Unit 2 Spent Fuel Pool with Credit for Inserted Neutron Absorber Panels, for NRC Review and Approval2015-01-28028 January 2015 Re-Submittal of Netco Report NET-300067-01, Criticality Safety Analysis of the Indian Point Unit 2 Spent Fuel Pool with Credit for Inserted Neutron Absorber Panels, for NRC Review and Approval NL-14-152, Entergy'S Expedited Seismic Evaluation Process Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights From...2014-12-22022 December 2014 Entergy'S Expedited Seismic Evaluation Process Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights From... ML14329A1952014-11-0404 November 2014 NET-300067-01, Rev. 0, Criticality Safety Analysis of the Indian Point Unit 2 Spent Fuel Pool with Credit for Inserted Neutron Absorber Panels NL-14-115, 10 CFR 50.59(d)(2) Summary Report for Indian Point, Units 1 and 2 April 1, 2012 to March 19, 20142014-09-18018 September 2014 10 CFR 50.59(d)(2) Summary Report for Indian Point, Units 1 and 2 April 1, 2012 to March 19, 2014 ML15166A0702014-08-31031 August 2014 Algonquin Incremental Market (Aim) Project, Phase 2 Acoustic Survey for Indiana Bats (Myotis Sodalis) and Northern Long-Eared Bats (Myotis Septentrionalis), August 2014 NL-14-110, Third Six-Month Status Report for the Implementation of Order EA-12-049 Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events2014-08-27027 August 2014 Third Six-Month Status Report for the Implementation of Order EA-12-049 Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events ML14141A5402014-05-0909 May 2014 Supplemental Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendations 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident ML14071A1832014-04-0101 April 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident NL-14-042, Entergy Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi.2014-03-31031 March 2014 Entergy Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi. NL-14-043, Entergy Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima.2014-03-31031 March 2014 Entergy Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima. ML14071A1982014-03-20020 March 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident ML14015A4172014-01-30030 January 2014 Staff Summary of the Steam Generator Tube Inservice Inspections for the Spring 2013 Refueling Outage ML14304A7512013-12-13013 December 2013 Unit 3 Coastal Zone Management Act Consistency Certification, Vol. II of III, Supplemental Information Regarding NYSDEC Record, Part 8 of 9 NL-13-133, 10 CFR 71.95 Report on Failure to Observe Certificate of Compliance Conditions for Radwaste Model 8-120B Cask Vent Port Leak Test Hold Time2013-10-0202 October 2013 10 CFR 71.95 Report on Failure to Observe Certificate of Compliance Conditions for Radwaste Model 8-120B Cask Vent Port Leak Test Hold Time ML13221A4172013-07-26026 July 2013 LTR-13-0662 - Susan Lerner, Common Cause New York Ltr Provides a Copy of Generating Influence, Entergy'S Political Spending and the Battle Over the Indian Point Nuclear Power Plant. ML14304A7522012-12-31031 December 2012 Unit 3 Coastal Zone Management Act Consistency Certification, Vol. II of III, Supplemental Information Regarding NYSDEC Record, Part 9 of 9 ML12346A3432012-11-20020 November 2012 Enclosure to NL-12-167 Seismic Walkdown Report - Page D-69 of 203 Through End ML12346A3422012-11-20020 November 2012 Enclosure to NL-12-167 Seismic Walkdown Report - Cover Through Page C-288 of 434 NL-12-167, Indian Point, Unit 2, Enclosure to NL-12-167 Seismic Walkdown Report - Cover Through Page C-288 of 4342012-11-20020 November 2012 Indian Point, Unit 2, Enclosure to NL-12-167 Seismic Walkdown Report - Cover Through Page C-288 of 434 NL-12-167, Indian Point, Unit 2, Enclosure to NL-12-167 Seismic Walkdown Report - Page D-69 of 203 Through End2012-11-20020 November 2012 Indian Point, Unit 2, Enclosure to NL-12-167 Seismic Walkdown Report - Page D-69 of 203 Through End NL-12-136, 10 CFR 72.48(d)(2) Report, Listing and Summary of Changes, Tests and Experiments2012-10-0101 October 2012 10 CFR 72.48(d)(2) Report, Listing and Summary of Changes, Tests and Experiments NL-14-002, Enclosure - NL-14-002, SAMA Engineering Project Cost Estimates Prepared by RCM Technologies2012-09-20020 September 2012 Enclosure - NL-14-002, SAMA Engineering Project Cost Estimates Prepared by RCM Technologies NL-12-009, Enclosure 1 to NL-12-009, Holtec International Licensing Report HI-2094289, Revision 52012-01-11011 January 2012 Enclosure 1 to NL-12-009, Holtec International Licensing Report HI-2094289, Revision 5 ML12040A3102012-01-11011 January 2012 Enclosure 1 to NL-12-009, Holtec International Licensing Report HI-2094289, Revision 5 ML11280A1212011-09-28028 September 2011 License Renewal Application - Completion of Commitment #30 Re Reactor Vessel Internals Inspection Plan NL-11-094, Request for Relief Request 14 - Code Case N-770-1 Weld Inspection Frequency Extension2011-08-0303 August 2011 Request for Relief Request 14 - Code Case N-770-1 Weld Inspection Frequency Extension NL-10-109, CFR 50.59(d) Report Listing and Summary Report of the Changes, Tests and Experiments Implemented Between 04/20/2008 and 04/12/20102010-10-12012 October 2010 CFR 50.59(d) Report Listing and Summary Report of the Changes, Tests and Experiments Implemented Between 04/20/2008 and 04/12/2010 ML1012704392010-05-0505 May 2010 Y020100187 - List of Historical Leaks and Spills at U.S. Commercial Nuclear Power Plants ML11299A1752010-02-0808 February 2010 Lr Hearing - Indian Point Task I Report - Deliverable (Redacted Version) ML0936410942009-12-30030 December 2009 Preliminary Power Authority of the State of New York, Indian Point No. 3, Nuclear Power Plant, Systems Interaction Study. Volume II ML0926401772009-08-28028 August 2009 Environmental Science and Engineering NL-09-095, Annual 10 CFR 50.46 Report for Calendar Year 2008 Emergency Core Cooling System Evaluation Changes2009-07-21021 July 2009 Annual 10 CFR 50.46 Report for Calendar Year 2008 Emergency Core Cooling System Evaluation Changes ML0905407042009-01-0909 January 2009 American Radiation Services, Inc. Laboratory Analysis Report No. ARS1-08-02367, Revised 01/09/2009 2022-01-13
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4B O R I S E OAK RIDGE INSTITUTE FOR SCIENCE AND EDUCATION I [uly 31. 2007 fir. Jim Kottan J.S.Nuclear Regulatory Commission 1 t?GeLdak Road (Ing of Prussia, PA 19406
SUBJECT:
REPORT FOR ANALYSES FOR SAMPLES FROM SET TWENTY-FOUR, FROM T H E INDIAN POINT POWER STATION, BUCHANAN, NEW I YORK
[INSPECTION REPORT NO. 050-247/2007-0031 [RFTA NO. 07-0011
>ear Mr. Icottan:
The Oak Ridge Institute for Science and Education (ORISE) recrived sct 24, consisting of six water amples, associated with the Indian Point Power Station on May 11, 2007. Sample analysis was initiated lased on your previous direction for handling samples from t h s licrnsee and modified based on a phone
- onversation with John \Vhtte on July 3,2007 and an e-mail from Stacie Sakai on July 9, 2007. Sample dentification and collection data for the samples addressed in thts report are presented in Table 1.
>amma spectroscopy, the hard-to-detect beras (iron-55, nickel-63, and tritium), technetium-99, total
.adiostrontium, alpha spectroscopy, plutonium-241, and carbon-14 data are provided in Tables 2 through 3, respectively. The pertinent procedure references are provided in each specific table.
3RISE's Quality Control (QC) requirements were met for these analyses. The QC fdes are available for Tour review upon requrst.
Wy contact information is listed below. You may also contact Wade Ivey at 865.576.9184 with any questions or comments.
Sincerely, Dale Condra, Manager zp
'>aboratory 75 I
RDC:LYTI.at W Znclosures s T. Carter, NRC/FSME/DLVIVIEP 7J8 E. &ox-Davin, NRC/FSME/TWFN SA23 J. \Y.htc, NRC Regiot E . Abelquist, ORISE lg VI S.Roberts, ORISE File 1697 Voice: 865.241.3242 Fax: 865.241.3248 E-mail: Dale.Condra @orau.org
TABLE 1 SAMPLE IDENTIFICATIONS AND COLLECTION DATA INDIAN POINT POWER STATION BUCHANAN, NEW YORK ORISE NRC Region I Collection Date Collection Sample ID Sample ID Time 1697WO142 Mw-54-38'-(00 1) 5/3/2007 16:19 1697W0143 Mw-54-59'-(001) 5/3/2007 16:45 1697W0144 Mw-54-125'-(001) 5/3/2007 14:18 1697W0145 Mw-54-146'-(001) 5/3/2007 1431 1697W0146 Mw-54-174'-(001) 5/3/2007 1443 1697WO147 Mw-54-192'-(001) 5/3/2007 15:OO Indian Point Power Station Projects/l697/Dara Tables/2007-07-31 Interim Data Tables 1697 Set 24
TABLE 2 CONCENTRATIONS OF SELECTED GAMMA EMITTING RADIONUCLIDES I N WATER SAMPLES BY GAMMA SPECTROSCOPY CP1, REVISION 15 INDIAN POINT POWER STATION B U C W A N , NEW YORK Radionuclide Concentrations, ORISE NRC Region I TPUs, and MDCs" @Ci/L)
Sample ID Sample ID CO-58 CO-60 cs-l34 cs-w7 1697YV0142 m-54-38'-(001) O.Ob k 2.0' , 3.5 2.3 k 3.1 , 3.8 0.5 f 2.4 , 3.8 2.4 ? 4.6 , 3.5 1697M0143 m-54-59'-(001) -1.1 2 2.3 , 3.8 -0.2 k 2.2 , 3.9 0.5 2 2.3 , 3.9 -1.0 L 2.2 , 3.6 1697YV0144 m-54-125'-(001) -1.1 k 1.8 , 3.1 -0.6 k 1.8 , 3.2 -2.6 -t 1.9 , 3.0 2.1 ? l>j , 3.0 1697YV0145 m-54-146'-(001) -1.9 k 2.8 , 4.1 2.4 ? 2.4 , 4.3 -0.8 ? 3.5 , 4.1 -1.0 k 2.3 , 3.8
- 1) 1697W0146 I m-54-174'-(001) I -1.2 ? 2.2 , 3.5 I 1.9 ? 2.1 , 3.81 -1.2 k 2.4 , 3.7) 1.3 k 4.6 , 3.3 I(
TABLE 3
~
Radionuclide Concentrations, ORISE N R C Region I TPUs, and MDCs" @Ci/L)
Sample ID Sample ID Fe-55h Ni-63' H-3*
1697W0142 MW-54-38'-(001) -13 k l g e , 33 6.1 i 4.4 , 7.2 1,000 i 210 , 290 I ,
I 169W0144 Mw-54-125'-(001) -6 f 19 , 33 5.2 ? 4.3 , 7.2 1,390 f 220 , 290
- 1697W0145 MW-54-146'-(001) -4 k 19 , 33 5.7 f 4.3 , 7.2 1,720 k 240 , 290 1697W0146 MW-54-174'-(001) -8 2 19 , 33 8.9 ? 4.4 , 7.2 1,830 ? 240 , 290 1697W0147 Mw-54-192'-(001) -2 k 19 , 33 6.4 k 4.4 , 7.2 1,860 +_ 240 , 290 InlanPmr Power Statlon I n t e r n Data Tables 1697 Set 24 Fra~ectr/l697/DaraTables/2007-07-31
TABLE 4 CONCENTRATIONS OF TECHNETIUM-99
, I N WATER SAMPLES BY LIQUID SCINTILLATION ANALYSIS AP5, REVISION 17; CP4, REVISION 3 INDIAN POINT POWER STATION BUCHANAN, NEW YORK Radionuclide ORISE NRC Region I Concentrations, Sample ID Sample ID TPUs, and MDCs"
@Q/L) 1697W0142 I MW-54-38'-(001) I 3.1 ? 7.6b , 13.0 (1 1697W0143 1 MW-54-59'-(001) I -1.2 ? 7.5 , 13.0 1 1 I 11I) 1697W0144 1697W0145 1697W0146 1
i MW-54-125'-(001)
MW-54-146'-(001)
Mw-54-174'-(001)
I 1
3.5
-0.3 4.5 i 7.7 k 7.5 k 7.7
, 13.0 13.0 13.0 1I 11 1697W0147 I MW-54-192'-1001) I -8.2 ? 7.4 , 13.0 (1 Indlan Point Power stauon Prqetcs/l697/Dara Tabler/Z007-07-31 I n t e r n Data Tables 1697 Set 24
TABLE 5 Radionuclide ORISE NRC Region I Concentrations, TPUs, and Sample ID Sample ID MDCS" @Ci/L) 1697W0142 Mw-54-38'-(001) 12.2 rt l.lb , 0.9 1697W0143 m-54-59'-(001) 3.09 i 0.67 , 0.84 1697W0144 m-54-125'-(001) 21.3 i 1.5 , 0.8 1697W0145 MW-54-146'-(001) 16.9 rt 1.3 , 0.9 1697W0146 MW-54-174'-(001) 19.4 rt 1.4 , 0.9 1697W0147 Mw-54-192'-(001) 22.5
- 1 6 , 0.9 Indian Point Power Station Pr4ects/l697/Data Tables/2007~07-31Inte- Data Tables 1697 Set 24
TABLE 6 ORISE NRC Region I Radionuclide Concentrations' (pCi/L for water)
Sample ID Sample ID Am-241 Cm-242 Cm-243/244 Np-237 1697W0142 Mw-54-38'-(001) 0.11 ? 0.15Ib , 0.32 -0.23 ? 0.19 , 0.41 0.02 ? 0.23 , 0.43 0.05 k 0.08 , 0.14 1697W0143 MW-54-59'-(001) 0.41 t 0.27 , 0.39 -0.02 ? 0.11 , 0.25 -0.07 ? 0.20 , 0.41 0.04 ? 0.08 , 0.16 1697W0144 MW-54-125'-(001) 0.09 0.13 , 0.22 0.00' ? 0.05 , 0.14 0.12 ? 0.09 , 0.05 -0.02 t 0.04 , 0.16 1697W0145 MW-54-146'-(001) 0.21 ? 0.22 , 0.36 0.05 2 0.09 , 0.15 -0.03 ? 0.16 , 0.32 0.02 2 0.09 , 0.19 1697W0146 MW-54-174'-(001) 0.07 ? 0.21 , 0.38 0.00 k 0.10 , 0.22 0.02 ? 0.16 , 0.32 -0.06 ? 0.09 , 0.24 1697W0147 MW-54-192'-(001) -0.04 ? 0.24 , 0.46 -0.08 ? 0.08 , 0.23 0.00 2 0.19 , 0.38 -0.08 ? 0.13 , 0.32 t
B
TABLE 6 (Continued)
CONCENTRATIONS OF SELECTED ALPHA EMITTING RADIONUCLIDES IN DISSOLVED FRACTIONS OF WATER SAMPLES AP11, REVISION 3; CP2, REVISION 12 INDIAN POINT POWER STATION BUCHANAN, NEW YORK i
TABLE 7 CONCENTRATIONS OF PLUTONIUM-241 I N DISSOLVED FRACTIONS OF WATER SAMPLES BY LIQUID SCINTILLATION ANALYSIS APlO, REVISION 3; CP4, REVISION 3 INDIAN POINT POWER STATION BUCHANAN, NEW YORK ORISE NRC Region I Radionuclide Concentrations, Sample ID SampleID TPUs, and MDCs" @Ci/L) 1697W0142 Mw-54-38'-(001) -2
- 37b 63 1697W0143 Mw-54-59'-(001) 8
- 34 59 Mw-54-125'-(001) 9 i 35 1697W0145 Mw-54-146'-(001) 5
- 34 59 1697W0146 Mw-54-174'-(001) 3
- 37 63 1697W0147 Mw-54-192'-(001) -6 t 36 62 T h e MDCS are afrer the comma.
bUn~ercmoesrepresmr h e 9594 confidence lwd, bascd on total propagated uncertainties Indian Point Power Station Prqlects/l697/Data Tables/2007-07-31 Inte-Data Tables 1697 Set 24
TABLE 8 ORISE NRC Region I Radionuclide Concentrations, Sample ID Sample ID TPUs, and MDCs' @Ci/L) 1697W0142 MW-54-38'-(001) -0.8 f 9.4b , 16.1 1697W0143 MW-54-59'-(001) -7.2 k 9.4 , 16.1 -
1697W0144 MW-54-125'-(001) -6.0 f 9.4 , 16.1 1697W0145 MW-54-146'-(001) 0.3 f 9.5 , 16.1 1697W0146 MW-54-174'-(001) -1.7 f 9.4 , 16.1 1697W0147 ME-54-192'-(001) -5.3 i 9.4 , 16.1 m e m c s are after the c o m a .
bUncertmties reprerent the 959b confidence level, based on totdpropagated uncert&mes.
In&m Pomr Power stauon Pr~ects/lG9l/DataTabler/2007-07-31 InteMl DataTables 1697 Set 24